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1.
用计算流体动力学程序CFX4.2对棒束定位格架通道内空气.水两相流体三维流动进行了数值模拟。在计算中,采用了考虑界面横向效应的两流体模型,用该模型计算模拟了通道的l/4区域和定位格架交混叶片.获得了流体区域的两相流速和相分布;并分析了定位格架交混叶片对流动和相分布的影响。结果表明.带定位格架棒束流道内空气-水两相流动数值模拟基本合理.该方法可用来初步分析复杂通道内的两相流动。  相似文献   

2.
采用两相计算流体动力学(CFD)分析的方法,对全长尺寸格架棒束通道内过冷沸腾两相流动进行了数值模拟。将模拟得到的棒束通道中心4个子通道的平均空泡份额与实验值进行对比发现,在高空泡份额区域与实验值符合较好;在低空泡份额区域,计算值略高于实验值。两相CFD方法模拟得到了棒束通道内空泡份额的详细分布,观察到格架上游空泡份额集中在加热棒的周围,但在格架下游,子通道中心的空泡份额增加,加热棒周围的空泡份额减小,间接地证明了格架对临界热流密度(CHF)的提升作用。  相似文献   

3.
陈曦  张虹 《原子能科学技术》2014,48(9):1589-1594
本文提出一种CFD方法用于评价压水堆燃料棒束定位格架两相搅混特性。针对两种典型的定位格架,采用CFX12.0进行了空气-水两相流动的数值模拟,并与采用氟里昂工质开展的临界热流密度(CHF)实验进行对比。结果表明,CFD方法可初步应用于评价格架下游汽泡的分布特性。  相似文献   

4.
棒束定位格架空泡份额分布特性实验研究   总被引:1,自引:0,他引:1  
带定位格架棒束通道内的空泡份额分布特性是反应堆热工水力特性研究的重要内容。对AFA 2G3× 3定位格架组成的棒束通道在空气 水两相流动工况下用RBI光学探针测得了通道内的横向空泡份额分布 ,分析了其横向分布的一般规律。结果表明 ,定位格架结构 ,特别是交混叶片对定位格架附近区域两相流动和空泡份额分布特性有重要影响 ,从而为进一步研究棒束定位格架加热工况下两相流动特性 ,发展新型高热工水力性能燃料组件打下基础  相似文献   

5.
采用两相计算流体动力学(CFD)方法进行带7道格架的5×5棒束两相性能研究,其中结构搅混格架(MG)和跨间搅混格架(MSMG)交替布置,计算考虑汽泡合并与破裂、热量传递,但不考虑相间的质量传递。为选择合理的两相模型参数,首先以带2道格架(MG、MSMG)的AFA3G燃料组件5×5棒束架为研究对象,对最大气泡直径、汽泡合并破裂系数、非曳力模型及曳力模型、入口气泡直径、入口空泡份额分布等进行了敏感性及不确定性分析。此后采用该两相模型设置,针对带7道格架的AFA3G燃料组件进行了两相性能研究,计算结果显示格架间的各项参数不存在完全一致的周期性,但同种格架上游的空泡份额分布具有一定的相似性,因此用于两相性能评价可计算带2~3道格架的棒束,该研究可用于带格架棒束两相计算的模型设置与几何规模选择,为下一步采用两相CFD计算建立燃料组件热工水力性能评价准则奠定了基础。最后比较了AFA3G燃料组件及改进型燃料组件两种格架的空泡分布特性,并从提高燃料组件临界热流密度(CHF)特性的角度对其进行评价,获得与实验一致的结论,证明了评价方法的正确性。   相似文献   

6.
《核动力工程》2016,(6):164-167
针对3×3棒束采用可视化实验技术研究棒束通道内气-液两相流动过程,获得了定位格架搅混翼附近的气泡行为特性。通过实验发现在搅混翼背流面存在气泡滞留的现象。在稳定工况下,滞留气泡的高度基本不变,滞留气泡相界面在流动、来流气泡合并过程中存在波动,并在液相的夹带下从滞留气泡末端分裂成多个小气泡。滞留气泡末端被液相夹带分裂是棒束通道中气泡尺寸变化的主要原因之一,并且分裂后的气泡尺寸小于来流气泡尺寸。在相同空泡份额条件下,随着液相流量的增加,滞留气泡高度增加,从滞留气泡上分裂的气泡尺寸相比来流气泡减小、数量增加;在相同液相流量条件下,随着空泡份额的增加,滞留气泡大小基本不变。来流气泡尺寸影响滞留气泡相界面的波动幅度,同时搅混翼背面存在滞留气泡时,气泡从搅混翼迎流面和背流面经过搅混翼时,在下游具有不同的运动特性,导致格架下游子通道间相态分布的差异性。  相似文献   

7.
压水堆燃料棒束通道内过冷沸腾分析   总被引:1,自引:1,他引:0  
使用Fluent14.5两流体模型中的RPI(Rensselaer Polytechnic Institute)壁面沸腾模型,对堆芯燃料棒束通道内过冷沸腾现象进行数值模拟,得到了通道内的流场、温度场以及空泡份额的分布,分析了定位格架和搅混翼的存在对热工水力特性的影响。数值结果表明,格架的存在会造成很大的压降,而搅混翼会对流场、温度场和空泡份额分布产生显著影响;RPI壁面沸腾模型的模拟结果与Bartolemei试验数据符合很好。  相似文献   

8.
竖直圆管内空泡份额径向分布特性形成机制   总被引:1,自引:0,他引:1  
在常温常压下,采用光纤探针测量方法对垂直上升大圆管中空气-水两相流动的空泡份额径向分布特性及形成机制进行研究。实验选用圆管直径为100 mm,气相、液相折算速度的范围分别为0.004~0.053 m/s和0.071~0.213 m/s。结果表明空泡份额径向分布随着气-液流量的不同,呈现出"核峰"或"壁峰"型分布特点;通过分析气泡所受到的横向升力和壁面力,表明二者对气泡横向运动的综合作用是造成空泡份额径向分布呈现出"核峰"或"壁峰"型分布的主要原因。  相似文献   

9.
研究两相流相间阻力特性对系统程序关键本构模型封闭具有重要意义。本文基于竖直圆管开展了空气-水两相流实验,采用四探头电导探针对空泡份额、气泡弦长和界面面积浓度等气泡参数的径向分布进行了测量。结果表明空泡份额和气泡弦长呈现“核峰型”分布,而界面面积浓度并没有表现出随流速的单调关系。进一步开发了泡状流和弹状流的相间曳力模型,考虑了液相表观流速与管径对气泡尺寸分布的影响,建立了临界韦伯数与不同液相流速的关系。计算得到的空泡份额和界面面积浓度与实验数据整体符合较好,验证了模型的可靠性,为两相流相间阻力特性研究提供参考意义。  相似文献   

10.
沈兰亭  柴翔  程旭 《核动力工程》2020,41(6):194-197
核电厂发生严重事故时可利用池洗效应去除泄漏的放射性气溶胶。对池洗过程进行两相数值模拟研究是有必要的,在使用两相计算流体力学(CFD)程序计算之前需要确定气泡注入点处的边界条件。基于整合池洗研究(IPRESCA)项目框架和流体体积法(VOF),对单个浸没孔气泡动力学特性进行数值模拟研究,捕捉浸没孔处气泡的大小、形状和脱离频率,并对气泡注入速度对气泡脱离频率的影响进行敏感性分析。利用DBSCAN聚类算法获得了气泡质心高度,并计算得到了不同高度的气泡上升速度。给出了平均空泡份额沿z轴方向的分布,以及平均空泡份额和平均混合速度在不同高度平面沿水平及径向的分布。   相似文献   

11.
为研究压水反应堆燃料组件棒束通道内的两相分布规律,设计并制造了适用于棒束通道的丝网传感器模块,开展了5×5棒束通道内空气-水泡状流的空泡分布测量实验,分析了棒束通道内空泡份额的分布规律及气泡尺寸对空泡分布的影响。实验结果表明,发生横升力方向反转的小气泡在壁面附近聚集、大尺寸气泡则聚集在子通道中心;常温常压下发生横升力方向反转的临界气泡直径在4~6 mm之间,证明了横升力模型在棒束通道中的适用性。   相似文献   

12.
The impact of gas in sodium flow on the temperature variation in an LMFBR rod bundle was studied in two types of experiments: (1) The gas fraction of the subchannels as well as the gas bubble spectra across the outlet of an unheated 61-rod bundle with wire spacers were measured in water/air flow. The distributions of the gas fractions at the inlet of the bundle were performed under uniform and non-uniform conditions. The results show that the distribution of the averaged gas fractions between the individual subchannels at the outlet of the bundle was almost the same as the distribution at the inlet. The measured bubble spectra show a dependency existing between the bubble frequencies, the bubble lengths, and the gas fraction in a subchannel. (2) A model for computing the transient temperature distributions within a heated rod was supported by experiments performed in a sodium/argon flow. For slug flow conditions a comparison indicates that the measured variations of wall temperatures can be well interpreted as being functions of the bubble contact time, rod power, and gas fraction in the flow.  相似文献   

13.
Applying a three-dimensional two-fluid model coupled with homogeneous multiple size group (MUSIG) approach, numerical simulations of upward subcooled boiling flow of water at low pressure were performed on the computational fluid dynamics (CFD) code CFX-10 with user defined FORTRAN program. A modified bubble departure diameter correlation based on the Unal's semi-mechanistic model and the empirical correlation of Tolubinski and Kostanchuk was developed. The water boiling flow experiments at low pressure in a vertical concentric annulus from reference were used to validate the models. Moreover, the influences of the non-drag force on the radial void fraction distribution were investigated, including lift force, turbulent dispersion force and wall lubrication force. Good quantitative agreement with the experimental data is obtained, including the local distribution of bubble diameter, void fraction, and axial liquid velocity. The results indicate that the local bubble diameter first increases and then decreases due to the effect of bubble breakup and coalescence, and has the maximum bubble diameter along the radial direction. Especially, the peak void fraction phenomenon in the vicinity of the heated wall is predicted at low pressure, which is developed from the wall repulsive force between vapor bubbles and heated wall. Nevertheless, there is a high discrepancy for the prediction of the local axial vapor velocity.  相似文献   

14.
The flow structure and bubble characteristics of steam–water two-phase upward flow were observed in a vertical pipe 155 mm in inner diameter. Experiments were conducted under volumetric flux conditions of JG<0.25 m s−1 and JL<0.6 m s−1, and three different inlet boundary conditions to investigate the developing state of the flow. The radial distributions of flow structure, such as void fraction, bubble chord length and gas velocity, were obtained by horizontally traversing optical dual void probes through the pipe. The spectra of bubble chord length and gas velocity were also obtained to study the characteristics of bubbles in detail. Overall, an empirical database of the multi-dimensional flow structure of two-phase flow in a large-diameter pipe was obtained. The void profiles converged to a so-called core-shaped distribution and the flow reached a quasi-developed state within a relatively short height-to-diameter aspect ratio of about H/D=4 compared to a small-diameter pipe flow. The PDF histogram profiles of bubble chord length and gas velocity could be approximated fairly well by a model function using a gamma distribution and log–normal distribution, respectively. Finally, the correlation of Sauter mean bubble diameter was derived as a function of local void fraction, pressure, surface tension and density. With this correlation, cross sectional averaged bubble diameter was predicted with high accuracy compared to the existing constitutive equation mainly being used in best-estimate codes.  相似文献   

15.
《Nuclear Engineering and Design》2005,235(10-12):1251-1265
Population balance equations combined with a three-dimensional two-fluid model are employed to predict subcooled boiling flow at low pressure in a vertical annular channel. The MUltiple-SIze-Group (MUSIG) model implemented in CFX4.4 is extended to account for the wall nucleation and condensation in the subcooled boiling regime. A model considering the forces acting on departing bubbles at the heated surface is formulated. This model provides the capacity of complex analyses on the bubble growth and departure for a wide range of wall heat fluxes and flow conditions.Comparison of model predictions against local measurements is made for the void fraction, bubble Sauter mean diameter and gas and liquid velocities covering a range of different mass and heat fluxes and inlet subcoolings. Good agreement is achieved with the local radial void fraction, bubble Sauter mean diameter and liquid velocity profiles against measurements. However, significant weakness of the model is evidenced in the prediction of the vapour velocity. Work is in progress to circumvent the deficiency of the MUSIG boiling model by the consideration of additional momentum equations to better represent the momentum forces acting on the range of bubble sizes in the bulk subcooled liquid.  相似文献   

16.
Visualization was performed for the vapor bubbles in water subcooled flow boiling in a vertical heated tube to measure simultaneously the void fraction and the four fundamental bubble parameters: nucleation site density, bubble release frequency, bubble lifetime and bubble size. Using the mass flowrate and liquid subcooling as the experimental parameters, the changes of void fraction and bubble parameters with the wall heat flux were measured. The results of image analysis showed that the vapor void fraction could be approximated by the function of nucleation site density and bubble lift-off diameter; the bubble lift-off diameter was more influential than the nucleation site density. It was hence concluded that the bubble lift-off diameter could be regarded as the key parameter to determine the vapor void fraction under the present experimental conditions. The strong relation of bubble lift-off diameter to superheated liquid layer thickness was indicated for the future model development studies of bubble lift-off diameter.  相似文献   

17.
18.
Lack of local void fraction data in a rod bundle makes it difficult to validate a numerical method for predicting gas–liquid two-phase flow in the bundle. Distributions of local void fraction and bubble velocity in each subchannel in a 4×4 rod bundle were, therefore, measured using a double-sensor conductivity probe. Liquid velocity in the subchannel was also measured using laser Doppler velocimetry (LDV) to obtain relative velocity between bubbles and the liquid phase. The size and pitch of rods were 10 and 12.5 mm, respectively. Air and water at atmospheric pressure and room temperature were used for the gas and liquid phases, respectively. The volume fluxes of gas and liquid phases ranged from 0.06 to 0.15 m/s and from 0.9 to 1.5 m/s, respectively. Experimental results showed that the distributions of void fraction in inner and side subchannels depend not only on lift force acting on bubbles but also on geometrical constraints on bubble dynamics, i.e. the effects of rod walls on bubble shape and rise velocity. The relative velocity between bubbles and the liquid phase in the subchannel forms a non-uniform distribution over the cross-section, and the relative velocity becomes smaller as bubbles approach the wall due to the wall effects.  相似文献   

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